The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

A Recent Look at CANDU Feeder Cracking: High Resolution Transmission Electron Microscopy and Electron Energy Loss Near Edge Structure (ELNES)

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_76 ◽

2017 ◽

pp. 1195-1215

Author(s):

C. D. Judge ◽

S. Y. Persaud ◽

A. Korinek ◽

M. D. Wright

Keyword(s):

Electron Microscopy ◽

Transmission Electron Microscopy ◽

High Resolution ◽

Energy Loss ◽

Electron Energy ◽

Edge Structure ◽

Transmission Electron ◽

Electron Energy Loss

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Feasibility Study of the Internal Zr/ZrO2 Reference Electrodes in Supercritical Water Environments

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_70 ◽

2017 ◽

pp. 1109-1122

Author(s):

Yu-Hsuan Li ◽

Yu-Ming Tung ◽

Tsung-Kuang Yeh ◽

Mei-Ya Wang

Keyword(s):

Feasibility Study ◽

Supercritical Water ◽

Reference Electrodes

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Corrosion Fatigue Behavior of Austenitic Stainless Steel in a Pure D2O Environment

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_60 ◽

2017 ◽

pp. 943-956

Author(s):

L. Yu ◽

R. G. Ballinger ◽

X. Huang ◽

M. M. Morra ◽

L. B. O’Brien ◽

...

Keyword(s):

Stainless Steel ◽

Austenitic Stainless Steel ◽

Corrosion Fatigue ◽

Fatigue Behavior

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The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_57 ◽

2017 ◽

pp. 895-911

Author(s):

D. J. Paraventi ◽

C. M. Brown ◽

L. B. O’Brien ◽

B. A. McGraw

Keyword(s):

Growth Rate ◽

Fatigue Crack ◽

High Temperature ◽

Crack Growth Rate ◽

Fatigue Crack Growth ◽

Crack Growth ◽

Fatigue Crack Growth Rate ◽

Stainless Steels ◽

Load Ratio ◽

Type 304

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NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_4 ◽

2017 ◽

pp. 55-65

Author(s):

Greg Oberson ◽

Margaret Audrain ◽

Jay Collins ◽

Eric Reichelt

Keyword(s):

Water Stress ◽

Stress Corrosion ◽

Stress Corrosion Cracking ◽

Corrosion Cracking ◽

High Chromium ◽

Primary Water

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Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_2 ◽

2017 ◽

pp. 15-25

Author(s):

Warren Bamford ◽

Steve Fyfitch ◽

Raj Pathania ◽

Paul Crooker

Keyword(s):

Crack Growth ◽

Testing Conditions ◽

Alloy 690 ◽

Plant Components

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Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_43 ◽

2017 ◽

pp. 669-680

Author(s):

C. Sun ◽

L. Malerba ◽

M. J. Konstantinovic ◽

F. A. Garner ◽

S. A. Maloy

Keyword(s):

Stainless Steels ◽

Ion Irradiation ◽

Void Swelling

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Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_36 ◽

2017 ◽

pp. 565-580

Author(s):

Jan Michalička ◽

Zhijie Jiao ◽

Gary Was

Keyword(s):

Stainless Steel ◽

Austenitic Stainless Steel ◽

Radiation Induced ◽

Cold Worked

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Role of Grain Boundary Cr5B3 Precipitates on Intergranular Attack in Alloy 600

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_23 ◽

2017 ◽

pp. 359-374

Author(s):

Daniel K. Schreiber ◽

Matthew J. Olszta ◽

Karen Kruska ◽

Stephen M. Bruemmer

Keyword(s):

Grain Boundary ◽

Alloy 600 ◽

Intergranular Attack

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Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors ◽

10.1007/978-3-319-67244-1_19 ◽

2017 ◽

pp. 293-305

Author(s):

Mi Wang ◽

Miao Song ◽

Gary S. Was ◽

L. Nelson

Keyword(s):

Stress Corrosion ◽

Stress Corrosion Cracking ◽

Corrosion Cracking ◽

Alloy 718 ◽

Cracking Behavior ◽

Primary Water

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The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Latest Publications

TOTAL DOCUMENTS

H-INDEX

Published By Springer International Publishing

A Recent Look at CANDU Feeder Cracking: High Resolution Transmission Electron Microscopy and Electron Energy Loss Near Edge Structure (ELNES)

Feasibility Study of the Internal Zr/ZrO2 Reference Electrodes in Supercritical Water Environments

Corrosion Fatigue Behavior of Austenitic Stainless Steel in a Pure D2O Environment

The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F

NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys

Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components

Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation

Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts

Role of Grain Boundary Cr5B3 Precipitates on Intergranular Attack in Alloy 600

Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water

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The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water ReactorsLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By Springer International Publishing

A Recent Look at CANDU Feeder Cracking: High Resolution Transmission Electron Microscopy and Electron Energy Loss Near Edge Structure (ELNES)

Feasibility Study of the Internal Zr/ZrO2 Reference Electrodes in Supercritical Water Environments

Corrosion Fatigue Behavior of Austenitic Stainless Steel in a Pure D2O Environment

The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F

NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys

Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components

Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation

Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts

Role of Grain Boundary Cr5B3 Precipitates on Intergranular Attack in Alloy 600

Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water

The Minerals, Metals & Materials Series - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Latest Publications